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  • 1
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 3 (1983), S. 185-197 
    ISSN: 1572-9591
    Keywords: neutronics ; fusion-fission ; hybrid reactors ; actinide multiplier ; LOTUS
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract An experimental fusion-fission hybrid research facility, known as LOTUS and located at the Swiss Federal Institute of Technology (EPFL), is nearing completion. The first series of experiments are likely to commence in early 1984. A whole series of neutronic investigations are already underway to assess the feasibility of experimentally testing various blanket concepts. The following analysis centers around the use of actinide wastes as multiplier for blankets with thorium oxide fuel. The multipliers considered are UO2, AmO2, and CmO2. The limited size of the experimental cavity coupled with the bulky, sealed 14 MeV (D, T)-neutron generator recommends the setting up of blankets in slab geometry. The analysis encompasses the corresponding confinement geometry configurations also for the sake of perspective. It is found that the neutronic performance of thorium oxide hybrid blankets improves radically both from the standpoint of fissile fuel production and energy multiplication in the presence of transplutonium actinides. It is also reported that the specific activities of tritium and233Pa are adequate for good counting statistics.
    Type of Medium: Electronic Resource
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  • 2
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 13 (1994), S. 59-67 
    ISSN: 1572-9591
    Keywords: Integral fusion neutronics ; LOTUS
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract In-system foil activation rates and tritium production rates were measured in an experimental lithium-lead module (EL2M)- major component being a 62-cm thick pseudo-cylindrical region containing lithium and lead pellets so arranged as to simulate Li17Pb8.3 eutectic—at fusion blanket neutronics facility LOTUS. Sets of two foils each—Zr and In—were irradiated at multiple locations in the central rod to measure90Zr(n,2n)89m+gZr and115In(n,n′)115mIn reaction rates. Tritium measurements were done using two techniques: off-line liquid scintillation technique of Dierck and online lithium glass scintillation technique, the latter technique providing only T6 (tritium from6Li). These measurements have been analyzed both by two-dimensional and three-dimensional transport codes DORT and MCNP, respectively. Though computed results broadly reproduce spatial profiles (along the central rod) of the measured quantities, differences as large as 50% are found.
    Type of Medium: Electronic Resource
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